Model for melt blockage (slug) relocation and physico-chemical interactions during core degradation under severe accident conditions
暂无分享,去创建一个
[1] L. Sepold,et al. Material Distribution in Light Water Reactor-Type Bundles Tested Under Severe Accident Conditions , 1997 .
[2] A. V. Palagin,et al. Modeling of chemical interactions of fuel rod materials at high temperatures II. Investigation of downward relocation of molten materials , 1998 .
[3] A. V. Berdyshev,et al. Modelling of Zr-O and U-Zr-O melts oxidation and new crucible tests , 2002 .
[4] J. P. Van Dorsselaere,et al. SARNET - Severe Accident Research Network of Excellence , 2010 .
[5] L. Sepold,et al. Chemical-physical behavior of light water reactor core components tested under severe reactor accident conditions in the CORA facility , 1997 .
[6] L. Benyahia,et al. Rheology of mixtures in the solidification range , 2006 .
[7] A. V. Berdyshev,et al. Modeling of chemical interactions of fuel rod materials at high temperatures I. Simultaneous dissolution of UO2 and ZrO2 by molten Zr in an oxidizing atmosphere , 1998 .
[8] A. V. Berdyshev,et al. Molten corium oxidation model , 2005 .
[9] A. V. Boldyrev,et al. Analysis of Molten Pool Physico-chemical Interactions and Interpretation of the Phebus FP Tests Observations , 2008 .
[10] Martin Steinbrück,et al. Experimental and calculational results of the experiments QUENCH-02 and QUENCH-03 , 2000 .